The Development Process of Human Machine Interface of Plant Protection System of a Small Modular Reactor

Tulis Jojok Suryono, Sigit Santoso, Restu Maerani, Pandhu Ardita Dharma Pratama

DOI: http://dx.doi.org/10.55981/tdm.2023.6934

Abstract


The Plant Protection System (PPS), which consists of Reactor Protection Systems (RPS) and Engineered Safety Actuated Systems (ESFAS), is one of the most important safety systems in nuclear reactors, including Small Modular Reactors (SMRs). The RPS generates a signal to trip the reactor if the measured reactor parameters exceed the trip setpoint, and then the ESFAS is actuated to mitigate the consequences of the accident by minimizing fuel damage and radioactivity release into the environment. Therefore, a comprehensive Human-Machine Interface (HMI) is essential for monitoring and controlling the PPS to ensure its reliability and enhance the operators' situational awareness. This study discusses the development process of the HMI for the digital PPS of an SMR. In this study, various standards, guidance, and design criteria for PPS and HMI are incorporated and applied to ensure that the proposed design meets the required level of reliability. In the first stage, the proposed design is intended for assessing the functionality and reliability of the PPS. Moreover, in the future, it will play an essential role in the design phase of the HMI for the PPS of an SMR in Indonesia.

Full Text:

PDF

References


1. Ahmed I., Jung J., Heo G. Design verification enhancement of field programmable gate array-based safety-critical I&C system of nuclear power plant. Nucl. Eng. Des. 2017. 317:232–41.

2. Nasiakou A., Bean R., Alamaniotis M. Development of human machine interface (HMI) for digital control rooms in nuclear power plants. 10th Int. Top. Meet. Nucl. Plant Instrumentation, Control. Human-Machine Interface Technol. NPIC HMIT 2017. 2017. 1:132–41.

3. International Atomic Energy Agency Advances in Small Modular Reactor Technology Developments, A Supplement to: IAEA Advanced Reactors Information System (ARIS). 2016.:400.

4. Hugo J. V., Gertman D.I. Development of operational concepts for advanced SMRS: The role of Cognitive Systems Engineering. ASME 2014 Small Modul. React. Symp. SMR 2014. 2014.(May)

5. Zohuri B., McDaniel P. Advanced Smaller Modular Reactors: An Innovative Approach to Nuclear Power. 2019.

6. Jung J., Ahmed I. Development of Field Programmable Gate Array-based Reactor Trip Functions Using Systems Engineering Approach. Nucl. Eng. Technol. 2016. 48(4):1047–57.

7. Wang X., Holbert K.E., Clark L.T. Single event upset mitigation techniques for FPGAs utilized in nuclear power plant digital instrumentation and control. Nucl. Eng. Des. 2011. 241(8):3317–24.

8. Shouman M.A., Saber A.S., Shaat M.K., El-Sayed A., Torkey H. Dynamic Modeling of Reactor Protection System in Nuclear Power Plant for Reliability Evaluation Based on State Transition Diagram. Menoufia J. Electron. Eng. Res. 2021. 30(1):13–21.

9. Muta H., Muramatsu K. Quantitative modeling of digital reactor protection system using Markov state-transition model. J. Nucl. Sci. Technol. 2014. 51(9):1073–86.

10. Wang C., Huang T., Gong A., Lu C., Yang R., Li X. Human-Machine Interaction in Future Nuclear Power Plant Control Rooms-A Review. IFAC-PapersOnLine. 2020. 53(5):851–6.

11. Seong P.H., Kang H.G., Na M.G., Kim J.H., Heo G., Jung Y. Advanced MMIS toward Substantial Reduction in Human Errors in NPPs. Nucl. Eng. Technol. 2013. 45(2):125–40.

12. O’hara J.M., Brown W.S., Persensky J.J., Lewis P.M. Human-System Interface Design Review Guidelines, NUREG-0700 Rev 3. 2020.

13. Santoso S., Suryono T.J., Maerani R., Sudarno, Pambudi Y.D.S., Dwiardika D. Preliminary Design of Human-Machine Interface for Control Room of Modular Reactor. AIP Conf. Proc. 2022. 2501(August)

14. IAEA Design of Instrumentation and Control Systems for Nuclear Power Plants-SSG-39. Saf. Stand. 2016.(SSG-39 Specific Safety Guide)

15. IAEA Safety of Nuclear Power Plants: Design. Specif. Saf. Requir. no SSR-2/1. 2000. 1

16. IAEA Human Factors Engineering in the Design of Nuclear Power Plants. IAEA SSG-51. 2019.


Refbacks

  • There are currently no refbacks.


PTKRN Digital Library Mendeley